JPS5877698A - Flashing device for reactor residual heat removable system - Google Patents
Flashing device for reactor residual heat removable systemInfo
- Publication number
- JPS5877698A JPS5877698A JP56174636A JP17463681A JPS5877698A JP S5877698 A JPS5877698 A JP S5877698A JP 56174636 A JP56174636 A JP 56174636A JP 17463681 A JP17463681 A JP 17463681A JP S5877698 A JPS5877698 A JP S5877698A
- Authority
- JP
- Japan
- Prior art keywords
- water
- residual heat
- reactor
- heat removal
- removal system
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physical Or Chemical Processes And Apparatus (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
本発明は、原子炉を停止させたときに、原子炉容器中の
冷却水を排水する原子炉残留熱除去系のフラッシング装
置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a flushing device for a nuclear reactor residual heat removal system that drains cooling water in a reactor vessel when the reactor is shut down.
原子炉残留熱除去系のフラッシング操作、即ち、原子炉
残留熱除去系の配管内保有水の交換操作は、配管内保有
水を排水口より排出した後、給水口より配管内に給水す
る。そして、配管内の水質を検査し、配管内保有水が原
子炉内の冷却水（炉水）と同程度のきれいな水質になる
壕で排水と給水とを繰り返えす。これは、残留熱除去系
の水を冷却水として・直円するためである。In the flushing operation of the reactor residual heat removal system, that is, the operation of exchanging the water held in the pipes of the reactor residual heat removal system, the water held in the pipes is discharged from the drain port, and then water is supplied into the pipes from the water supply port. The water quality in the pipes is then inspected, and the water is drained and supplied repeatedly in the trench until the water held in the pipes is as clean as the cooling water (reactor water) inside the reactor. This is because the water in the residual heat removal system is used as cooling water to form a right circle.
ところが、従来の残留熱除去系の給水口、排水口等に設
けられている弁は手動弁であるため、フラッシング操作
をするときには、操作員が弁の設けられている場所まで
行き、手動により弁を開閉しなければならない。しかも
、給水弁、排水弁等がそれぞれ異った場所にあり、また
、それぞれの設置階が異なり、高低のある場所に設けら
れている。このため、原子炉停止時の繁忙のときに、４
約２時間から４時間もかかるフラッシング操作に大変な
人数（２〜３人）を割かなければならないし、まだ、操
作員の大変な肉体労働による労力を必要とするばかりで
なく、炉水からの放射線による被曝も無視できない。However, the valves installed at the water inlet, drain, etc. of conventional residual heat removal systems are manual valves, so when performing flushing operations, the operator must go to the location where the valve is installed and manually close the valve. must be opened and closed. In addition, the water supply valves, drain valves, etc. are located at different locations, and are installed on different floors and at different heights. For this reason, during the busy period of reactor shutdown, 4
A large number of people (2 to 3 people) must be devoted to the flushing operation, which takes about 2 to 4 hours, and not only does it still require a lot of manual labor from the operators, but it also requires a lot of effort from the reactor water. Exposure to radiation cannot be ignored either.
本発明は、前記従来技術の欠点を解消するだめになされ
たもので、フラッシング操作に要する労力を低減できる
原子炉残留熱除去系のフラツ／ング装置を提供すること
を目的とする。The present invention has been made to overcome the drawbacks of the prior art, and an object of the present invention is to provide a flushing device for a nuclear reactor residual heat removal system that can reduce the labor required for flushing operations.
本発明は、原子炉容器内に冷却水を供給する管路の給水
口部とこの冷却水を排出する排水口部とに電動弁を設け
、前記管路に電導度肝と水位、凍出計とを設けるととも
に、この祇導度計と水位検出計との、〆出信号により前
記’ｌ！ｒ岨動弁全動弁して、自動的にフラノソング操
作が行えるように構成したものである。The present invention provides electrically operated valves at the water inlet of a pipe that supplies cooling water into the reactor vessel and at the drain port that discharges this cooling water, and provides electrical conductivity, water level, and freezing meters in the pipe. At the same time, the above-mentioned 'l! It is constructed so that the r-operated valve is fully operated and the flannel song operation can be performed automatically.
本発明に係る原子炉残留熱除去系のフラツ／ング装置の
好ましい実施例を添付図面に従って詳細する。DESCRIPTION OF THE PREFERRED EMBODIMENTS A preferred embodiment of a floating device for a nuclear reactor residual heat removal system according to the present invention will be described in detail with reference to the accompanying drawings.
第１図は、本発明に係る原子炉残留熱除去系の７ラツシ
ング装置の実施例の説明図である。FIG. 1 is an explanatory diagram of an embodiment of a seven lashing device for a nuclear reactor residual heat removal system according to the present invention.
第１図において原子炉容器１０を冷却する炉水け、再循
＞ｊＪ系１２において冷却され、ポンプ１４によって原
子炉容器１０内に送られる。そして、再循環系１２には
、残留熱除去系１６から炉水の供給を受けるだめの１１
給管１８と、炉水を残留熱除去系に導く排水管２０とが
取り付けられている。In FIG. 1, the reactor water that cools the reactor vessel 10 is cooled in a recirculation>jJ system 12 and sent into the reactor vessel 10 by a pump 14. The recirculation system 12 includes a reservoir 11 which receives reactor water supply from the residual heat removal system 16.
A feed pipe 18 and a drain pipe 20 are attached that lead the reactor water to the residual heat removal system.
なお、供給管１８は、切換弁２２を介して残留熱除去系
１６の給水側主管２４に接続され、また、再循環系１２
と残留熱除去系１６との遮断を完全にするため２つの隔
離弁２６が取り付けられている。また、給水側主管２４
には、給水支管２８が配管され、給水口部に逆止弁３０
と図示しない自動制御装置により開閉される心動弁３２
とが設けられている。さらに、給水側主管２４には、べ
／ト管３４が取り付けられており、このベント管３４に
は手動弁３８と前記自動制御装置により開閉される電動
弁４０と前記自動制御装置に検出信号を送る水位検出計
４２とが設けられ、ベント管３４の先端はドレン口４４
となっている。The supply pipe 18 is connected to the water supply side main pipe 24 of the residual heat removal system 16 via a switching valve 22, and is also connected to the water supply side main pipe 24 of the residual heat removal system 16.
Two isolation valves 26 are installed to completely isolate the residual heat removal system 16 from the residual heat removal system 16. In addition, the water supply side main pipe 24
A water supply branch pipe 28 is installed at the water supply port, and a check valve 30 is installed at the water supply port.
and a cardiac valve 32 that is opened and closed by an automatic control device (not shown).
and is provided. Further, a vent pipe 34 is attached to the water supply side main pipe 24, and this vent pipe 34 includes a manual valve 38, an electric valve 40 that is opened and closed by the automatic control device, and a detection signal to the automatic control device. A water level detector 42 is provided, and the tip of the vent pipe 34 is connected to a drain port 44.
It becomes.
他方、排水管２０は、切換弁４６を介して残留熱除去系
１６の排水側主管４８に接続されている。On the other hand, the drain pipe 20 is connected to a drain side main pipe 48 of the residual heat removal system 16 via a switching valve 46 .
そして、排水管２０には、残留熱除去系１６との遮断を
図る２つの隔離弁５０が取り付けられていると共に、手
動弁５２と前記図示しない自動制御装置により開閉され
る電動弁５４とを介して注水口に通じる注水管５６が接
続されている。なお、排水側主管４８には、ポンプ５８
と逆止弁６０とが設けられており、排水側主管４８の末
端（排水管２０の反対側端）は、前記給水側主管２４が
接続されている熱交換器６２に接続されている。さらに
、排水側主管４８の逆止弁６０と熱交換器６２との中間
には、末端が排水口部であるドレン口６４となっている
ドレン管６６が配管されている。このドレン管６６には
、手動弁６８、前記自動制御装置により開閉される電動
弁７０及び前記自動制御装置に検出信号を送る電導度肝
７２が設けられている。Two isolation valves 50 are attached to the drain pipe 20 to isolate it from the residual heat removal system 16, and a manual valve 52 and an electric valve 54 that is opened and closed by the automatic control device (not shown) are connected to the drain pipe 20. A water injection pipe 56 leading to a water injection port is connected to the water injection port. In addition, a pump 58 is installed in the drain side main pipe 48.
and a check valve 60, and the end of the drain side main pipe 48 (the end opposite to the drain pipe 20) is connected to a heat exchanger 62 to which the water supply side main pipe 24 is connected. Furthermore, a drain pipe 66 whose end is a drain port 64 is installed between the check valve 60 and the heat exchanger 62 of the drain side main pipe 48 . This drain pipe 66 is provided with a manual valve 68, an electric valve 70 that is opened and closed by the automatic control device, and a conductive valve 72 that sends a detection signal to the automatic control device.
なお、符号７４は、図示しない原子炉格納容器の周囲に
配設された圧力抑制室であって、原子炉格納容器内にお
ける一次系配管の破断により、原子炉格納容器内に噴出
する水蒸気を導いて冷却、凝縮させるようになっており
、隔離弁７６が設けられた管７８によって排水側主管４
８と通じている。Reference numeral 74 denotes a pressure suppression chamber (not shown) disposed around the reactor containment vessel, which guides water vapor spouted into the reactor containment vessel due to a rupture of the primary system piping within the reactor containment vessel. The drain side main pipe 4 is cooled and condensed by a pipe 78 equipped with an isolation valve 76.
It is connected to 8.
まだ、前記自動制御装置は、自動シーケンス制御をなし
、第２図に示すように自動／−ケンス装置８０に全部の
制御棒が原子炉に挿入されたことを示す挿入信号８２が
送られてくると、電動弁７０を開き電導度肝７２によっ
て排水の電気伝導度を検出し、電気伝導度が一定値以下
になるまで残留熱除去系１６の給排水を繰り返えし、排
水中の電気伝導度が一定値以下になると完了表示８４を
点灯してフラッシング操作を終了する。Still, the automatic control device performs automatic sequence control, and as shown in FIG. 2, an insertion signal 82 indicating that all control rods have been inserted into the reactor is sent to the automatic/can control device 80. Then, the electric valve 70 is opened, the electrical conductivity of the wastewater is detected by the conductivity gauge 72, and the supply and drainage of the residual heat removal system 16 is repeated until the electrical conductivity falls below a certain value, and the electrical conductivity of the wastewater is When the value falls below a certain value, the completion display 84 is turned on and the flushing operation is ended.
上記の如く構成された実施例の残留熱除去系のフラッシ
ング操作は、次のとおりである。The flushing operation of the residual heat removal system of the embodiment configured as described above is as follows.
原子炉の停止を知らせる全制御棒の挿入信号８２が自動
シーケンス装置８０に入力されると、自動ンーケンス装
置８０は、所定の時間、即ち、原子炉容器１２内の圧力
が原子炉停止時の定常圧力に低下するまでの時間（約２
〜３時間）が経過すると、ベント管３４の電動弁４０を
開き、次に、ドレン管６６の電動弁７０を開く。このた
め、ベント管３４から残留熱除去系１６内に空気が流入
するのに伴い、給水側主管２４と排水側主管４８との管
内保有水がドレン管６６を通りドレンロ６４から排出さ
れる。この篩、ドレンＷ６６をｆｉれる排水中の一気伝
導度が電導度肝７２により検出され、その検出信号が第
２図に示すように自動シーケンス装置８ｏに送られる。When the all-control rod insertion signal 82 informing the shutdown of the reactor is input to the automatic sequence device 80, the automatic sequence device 80 performs a process for a predetermined period of time, that is, when the pressure inside the reactor vessel 12 reaches the steady state at the time of the reactor shutdown. The time it takes for the pressure to drop (approximately 2
3 hours), the motor-operated valve 40 of the vent pipe 34 is opened, and then the motor-operated valve 70 of the drain pipe 66 is opened. Therefore, as air flows into the residual heat removal system 16 from the vent pipe 34, the water held in the water supply side main pipe 24 and the drain side main pipe 48 passes through the drain pipe 66 and is discharged from the drain hole 64. The conductivity of the waste water flowing through the sieve and drain W66 is detected by the conductivity gauge 72, and the detection signal is sent to the automatic sequence device 8o as shown in FIG.
また、自動シーケンス装置８ｏは、予め設定された残留
熱除去系１６の管内保有水が全部排出されるに要する時
間（例えば３０分等）が経過すると、ドレン管６６の電
動弁７ｏを閉じ、給水支管２８の電動弁３２と注水管５
６の電動弁５４とを開く。従って、残留熱除去系１６内
に給水支管２８と注水管５６とから水が供給され、系内
の空気がベント管３４を通りドレン口４４がら大気中に
放出される。そして、供給された水が残留熱除去系１６
を満し、ベント管３４から手動弁３８、電動弁４０を経
て水位検出計４２に達し、水位検出系４２が水位を検出
して残留熱除去系１６の水はりが終了したことを知らせ
る検出信号を自動ノーケン装置８０に送る。自動シーケ
ンス装置８゜は、水位検出計からの検出信号を受けると
、電動弁３２．５４を閉じ水の供給を停止する。In addition, when a preset time (for example, 30 minutes, etc.) required for all the water retained in the pipe of the residual heat removal system 16 to elapse, the automatic sequence device 8o closes the electric valve 7o of the drain pipe 66 and supplies water. Electric valve 32 of branch pipe 28 and water injection pipe 5
6, the electric valve 54 is opened. Therefore, water is supplied into the residual heat removal system 16 from the water supply branch pipe 28 and the water injection pipe 56, and the air in the system passes through the vent pipe 34 and is discharged into the atmosphere through the drain port 44. Then, the supplied water is transferred to the residual heat removal system 16.
is reached from the vent pipe 34 through the manual valve 38 and the electric valve 40 to the water level detector 42, and the water level detection system 42 detects the water level to generate a detection signal indicating that the residual heat removal system 16 has finished filling with water. is sent to the automatic noken device 80. When the automatic sequence device 8° receives a detection signal from the water level detector, it closes the electric valve 32.54 and stops the water supply.
このとき、自動シーケンス装置は、前記した電導度肝７
２から受けた検出信号が所定の値以上、即ち、排水の電
気伝導度が不純吻の含まれていない炉水の水質を示す電
気伝導度以上であるときは１ドレン管６６のに動弁７０
を再び開き、排水をしなから電導度肝７２により排水の
電気伝導度を検出する。At this time, the automatic sequence device performs the above-mentioned conductivity level 7.
When the detection signal received from the drain pipe 66 is equal to or higher than a predetermined value, that is, the electrical conductivity of the waste water is equal to or higher than the electrical conductivity indicative of the quality of reactor water that does not contain impurities, the valve 70 of the drain pipe 66 is activated.
After the drain is opened again and the water is drained, the electrical conductivity of the waste water is detected by the conductivity gauge 72.
上記の排水、水はり過程は、電導度肝７２の検出信号が
所定の値以下になるまで繰り返えされる。The above-mentioned draining and filling processes are repeated until the detection signal of the conductivity indicator 72 becomes equal to or less than a predetermined value.
そして、自動シーケンス装置８０は、電導度肝７２から
受けた検出信号が所定の値以下になると、残留熱除去系
１６内の水はりの終了を知らせる水位検出計４２からの
検出信号により、給水支管２８の電動弁３２と注水管５
６の電動弁５４を閉じると共に、ベント管３４の電動弁
４０を閉じ、第２図に示すように完了表示８４を点灯す
る。これにより残留熱除去系１６のフラッシング操作が
完了する。Then, when the detection signal received from the conductivity gauge 72 becomes equal to or less than a predetermined value, the automatic sequence device 80 detects the water supply branch pipe 28 using the detection signal from the water level detector 42 that indicates the end of water filling in the residual heat removal system 16. electric valve 32 and water injection pipe 5
At the same time, the electric valve 40 of the vent pipe 34 is closed, and the completion display 84 is turned on as shown in FIG. This completes the flushing operation of the residual heat removal system 16.
従って、残留熱除去系のフラッシング操作のために特別
の操作員を必要とせず、捷た、従来問題となっていたフ
ラッシング操作に能う操作員の放射線被曝を避けること
ができる。Therefore, a special operator is not required for the flushing operation of the residual heat removal system, and it is possible to avoid radiation exposure of the operator who can perform the flushing operation, which has been a problem in the past.
なお、自動シーケンス装置８０は、リセツ１４能を有し
ており、任意の時にリセットをすることができる。従っ
て、原子を停止させた場合において、残留熱除去系１６
のフラッシング操作が不要のときは、フラッシング操作
が全制御棒の挿入完了を知らせる挿入信号８２が自動シ
ーケンス装置８０に入力された後、一定時間（約２〜３
時間）を経過してから行なわれるようになっているので
、この時間内にフラッシング解除の操作をし、自動シー
ケンス装置８０のリセットを行うことができる。また、
フラッシング操作の進行中においても、必要なときにフ
ラッシング操作を停止させ、自動シーケンス装置のリセ
ットをすることができる。Note that the automatic sequence device 80 has a reset function and can be reset at any time. Therefore, when the atoms are stopped, the residual heat removal system 16
When the flushing operation is not required, the flushing operation is performed for a certain period of time (approximately 2 to 3
Since the flushing is performed after a period of time has elapsed, the automatic sequence device 80 can be reset by canceling the flushing within this time. Also,
Even while the flushing operation is in progress, it is possible to stop the flushing operation and reset the automatic sequencer when necessary.
前記実施例においては、電導度肝７２をドレン管６６に
設けた場合について説明したが、電導度肝は他の場所、
例えば排水側主管４８等に設けてもよい。In the embodiment described above, the case where the conductivity scale 72 was provided in the drain pipe 66 was explained, but the conductivity scale was provided in other places,
For example, it may be provided in the drain side main pipe 48 or the like.
以上説明したように本発明によれば、残留熱除去系の給
水口部と排水口部とに電動弁を設け、自動制御装置によ
り開閉するようにしたので、残留熱除去系のフラッシン
グ操作に要する労力を低減することができる。As explained above, according to the present invention, electric valves are provided at the water supply port and drain port of the residual heat removal system, and the valves are opened and closed by an automatic control device. Labor can be reduced.
第１図は本発明に係る原子炉残留熱除去系のフラッシン
グ解除の実施例の説明図、第２図は前記実施例に用いら
れる自動制御の政略を示す図である。FIG. 1 is an explanatory diagram of an embodiment of flushing cancellation of a nuclear reactor residual heat removal system according to the present invention, and FIG. 2 is a diagram showing a strategy of automatic control used in the embodiment.
Claims (1)
冷却水を排出する排水口部とが設けられた管路を有する
原子炉残留熱除去系のフラッシング装置において、前記
給水口部に設けた電動弁と、前記排水口部に設けた電動
弁と、前記管路に取り付けた成導度計と、前記管路に設
けた水位、演出計と、前記電導度計と前記水位検出計と
の検出信号により前記各醒励弁を開閉する自動制＃装置
を設けたことを特徴とする原子炉残留熱除去系のフラッ
シング装置。1. In a flushing device for a reactor residual heat removal system having a pipe line provided with a water supply port for supplying cooling water into the reactor vessel and a drain port for discharging this cooling water, the water supply port a motor-operated valve provided at the drain port, a conductivity meter attached to the conduit, a water level/direction meter disposed in the conduit, the conductivity meter and the water level detection A flushing device for a nuclear reactor residual heat removal system, characterized in that an automatic control device is provided for opening and closing each of the flushing valves based on a detection signal from a reactor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56174636A JPS5877698A (en) | 1981-11-02 | 1981-11-02 | Flashing device for reactor residual heat removable system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56174636A JPS5877698A (en) | 1981-11-02 | 1981-11-02 | Flashing device for reactor residual heat removable system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5877698A true JPS5877698A (en) | 1983-05-11 |
| JPS645671B2 JPS645671B2 (en) | 1989-01-31 |
Family
ID=15982050
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56174636A Granted JPS5877698A (en) | 1981-11-02 | 1981-11-02 | Flashing device for reactor residual heat removable system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5877698A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0509923A1 (en) * | 1991-04-17 | 1992-10-21 | Framatome | Pressurized water nuclear reactor comprising a primary coolant draining system with an intrinsic determined low water level safety |
| FR2700060A1 (en) * | 1992-12-31 | 1994-07-01 | Brand | System and method for controlling the level of coolant in a nuclear reactor |
| WO1999054886A1 (en) * | 1998-04-17 | 1999-10-28 | Abb Combustion Engineering Nuclear Power, Inc. | Shutdown cooling system safety feed system |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5013705A (en) * | 1973-06-11 | 1975-02-13 | ||
| JPS5360492A (en) * | 1976-11-10 | 1978-05-31 | Toshiba Corp | Cooling system at reactor stopping time |
| JPS55143596U (en) * | 1979-04-03 | 1980-10-15 |
-
1981
- 1981-11-02 JP JP56174636A patent/JPS5877698A/en active Granted
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5013705A (en) * | 1973-06-11 | 1975-02-13 | ||
| JPS5360492A (en) * | 1976-11-10 | 1978-05-31 | Toshiba Corp | Cooling system at reactor stopping time |
| JPS55143596U (en) * | 1979-04-03 | 1980-10-15 |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0509923A1 (en) * | 1991-04-17 | 1992-10-21 | Framatome | Pressurized water nuclear reactor comprising a primary coolant draining system with an intrinsic determined low water level safety |
| FR2675618A1 (en) * | 1991-04-17 | 1992-10-23 | Framatome Sa | DEVICE FOR DRAINING THE PRIMARY CIRCUIT OF A NUCLEAR REACTOR COOLED BY PRESSURE WATER WITH LOW LEVEL INTRINSIC SAFETY. |
| FR2700060A1 (en) * | 1992-12-31 | 1994-07-01 | Brand | System and method for controlling the level of coolant in a nuclear reactor |
| WO1999054886A1 (en) * | 1998-04-17 | 1999-10-28 | Abb Combustion Engineering Nuclear Power, Inc. | Shutdown cooling system safety feed system |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS645671B2 (en) | 1989-01-31 |
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